Demonstration reactors

National programs are underway to develop and deploy the reactor and applications in China, France, South Korea, and United States [35-38]. Many more countries are participating in R D through the High Temperature Reactor Technology Network of the European Union [39] and the GIF including the 10 member countries [40]. Builds of full-scale commercial demonstration reactors are actively planned in several countries such as South Africa [41] and the United States [38]. 

Hamilton, David P, EDITOR "A Fusion First", Science Scope, Science, Vol. 254, No. 5034, November 15,1991, Page 927 Sweet, William, Super Powers Promote Design Effort for Fusion Demonstration Reactor", Physics Today, January 1988, Page 75 Thon en, D. E., "Charging Their Way Toward Fusion , Science News, December 21, 1985, Page 389... 

Stable operation of the demonstration reactor BN-600 in Russia with a nominal power output of 600MW(e) for 20 years and an average load factor of 72%, successful operation of the prototype reactors BN-350 in Kazakshstan and Phenix in France as well as the reliable operation of MOX fuel at high bumup (20% witti an irradiation dose in excess of 160 displacement per atom (dpa) in the cladding) in PFR (UK) and Phenix, are milestone in the implementation of LMFR technology. 

Review of various anomalous events and abnormal operation experience gained in the process of Russian fast reactors operation is given in the paper. The main information refers to the BN-600 demonstration reactor operation. 

Three sodium cooled fast reactors are currently in operation in Russia, namely BR-10 and BOR-60 experimental reactors and BN-600 demonstration reactor NPP. NPP with the BN-350 prototype reactor is now on the territory of Kazakhstan Republic. However Russian institutions and enterprises which participated in the design development and construction of the BN-350 reactor are now involved in its operation. 

Russian experience gained on operation of experimental and prototype fast reactors (BR-10, BOR-60, BN-350 and BN-600) is rather good. Stable operation of the demonstration reactor... 

ER Experimental Reactor DR Demonstration Reactor PR Powered Reactor FS Final Shutdown S Stopped 10 In operation P Project... 

In parallel with the operation of IFMIF, the DEMO design (Demonstration Reactor), should get to an engineering demonstration and supply all the necessary elements for an economic evaluation of the process. 

Excluding military and space reactors, approximately 20 sodium-cooled fast reactors have been built in a variety of sizes and configurations. These vary from small test reactors to the French Super-Phenix plant, which had an output of 1240 MW(e). In the United States, several fast reactors were built. These included the EBR-II and the Fast-Flux Test Facility (FFTF)—a 400-MW(t) reactor. The Clinch River Breeder Reactor Plant (CRBRP), a commercial demonstration reactor, was designed and partly built before being cancelled. These machines provide a large experience base in refueling operations (Romrell et al., 1989 Althaus and Brahy, 1987). 

A brief description of the development of forging components in the Japan Steel Works (JSW) is as follows. JSW supplied the plates for the RPVs in the Japan Power Demonstration Reactor (JPDR) of the Japan Atomic Energy Research Institute (JAERI) in 1961 and the Japan Atomic... 

PNC conducted design study on a 600MWe-size plant for 1990 - 1991. In 1992, JAPC and PNC discussed on the mutual design results to improve the demonstration reactor design study. 

PNC is planning to construct another ATR line at PFPF so as to produce fuels for the ATR demonstration reactor. 

It has been anticipated that the worldwide development of LMR technology will be completed around 2010 when most demonstration reactors will have been finished in construction. The commercialization of LMRs has been expected to be realized aroimd 2025 -2030. In this context, the LMR R D programs have been started in Korea at this time, and we have the objective to establish an advanced LMR design concept in order to contribute to a certain amount of worldwide LMR R feD works and ultimite LMR industry. 

Then, Enrope came to the forefront. The UK constructed and operated PFR, the first prototype FR in Europe, following DFR. Now, the PFR has finished its roles and is in the process of decommissioning. Meanwhile, France constmcted and operated a demonstration reactor Snperphenix based on the experience of constmction and operation of Rapsodie and Phenix, bnt it is closed. 

Studies in the last decade have demonstrated reactor performance improvement over the optimal steady state under forced time-varying liquid flow rates [2-4]. In this mode of operation, the bed is periodically flushed with liquid, while the gas phase is fed continuously. TTie liquid-phase adds a transport resistance that is often rate controlling for sparingly soluble gaseous reactants. The liquid-phase however is in most cases essential to the system and can not be eliminated. 

The function of the hydraulic pressure valve for the PRSS was successfully confirmed by a test with a half scale model. Since there is no operating experience of a reactor without control rods, construction of a demonstration reactor is considered necessary. 

The Demonstration Reactor Benchmark Critical Assemblies Program, C. E. Till, W. G. Davey (ANL>... 

ZPPR Assembly 2 is toe first assembly in toe overall prosram. It is a clean version of a generalized demonstration reactor configuration. It is a two-zone plutonium, uranium), Oi-fueled core, with a 60/50 volume split between the two zones, and a ratio of plutonium contents of 1,5 tetween toe outer and inner zones. The axial ajid radial blankets have appropriate volume fractious of depleted UOi and sodium, and are surrounded, in turn, by a steel reflector. 

Predicted Characteristics with Actual Observation for the Demonstration Reactor Benchmark Assembly ZPPR-2, E. E. Kcnset, R. J. Norris, A. P. Olson, N. C. Paik (ANL-, Idaho)... 

ZPPR Assembly 2 is part of the demonstration reactor benchmark critical assembly program. E is a Ihrge, zoned, critical assembly designed to simulate the compositions and configurations of the LMFBR demonstratioh> plants. 

A series of small-saniple reactivity measurements Was made on ZPFR Assembly 2, the demonstration plant benchmark critical assembly, and conqnred with analytical results. This assembty is a two-zone system which reproduces many of the essentials of current demonstration reactor concepts, and has a nmch larger critical mass (1018.4 kg Pu Pu) and critical volume (2376.5 liter) than any other plutonium-faeled critical facility yet buUt. ... 

Initial Experimental Results from ZPR-6 Assen ly 7, The Single-Zone Demonstration Reactor Benchmark Assembly, L. G. LeSage, E. M. Bohn, J. E. Marshall, R. A. Karam, C. . Till, R. A. Leans, M, Salvatores (ANL)... 

LMFBR Demonstration Reactor Benchmark Critical Experiments Program—Initiol P iate-Rod Heterogeneity Measurements, R. A. 

The Seven Critical Configurations of the ZPPR Demonstration Reactor BenOhnnark Program, R. G. Palmer, W, G. DaVfiy, P. L Amundson (ANL-Idako)... 

Calcnlated and Experimental SubcrtticaUty Parameters for the ZPPR 3 Demonstration Reactor benchmark... 

C. E. TILL et al., ZPR-6 Assemblies 6A and 7 Benchmark S ciGcation for the Two Large Single-Core-Zone Critical Assemblies— U-Fueled Assembly 6A and Phitonium-Ftaeled Assembly 7—LMFBR Demonstration Reactor Critical Experiment Program, Applied Physics Division Annual Report, July 1, 1970 to June 30, 1971, ANL-7910, pp. 86-102. Argonne National Lab. 

W. G. DAVEY, The Demonstration Reactor Benchmark Program, fVoc. Cbrt/. New Dev. in Reactor Phys. and Shieldinz, CONF-720901, p. 789, USAEC(I972). 

In the United States, the development of nuclear reactors for nuclear power production began after World War II. Engineers and scientists involved in the development of the atomic bomb could see that the nuclear reactor would provide an excellent somce of heat for production of steam that could be used for electricity generation. Work began at Argonne National Laboratory (ANL), Lemont, Illinois, and at Oak Ridge National Laboratory, Tennessee, on various research and demonstration reactor projects. 

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